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Requirements for reactor heat removal capability during outage of nuclear power plants

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1.2 This Standard covers only fuel cooling within the reactor core and does not cover spent fuel pool cooling, off-reactor fuelling operations, or the completely defueled core state.

1.3 The term "outage" refers to the following reactor states: a) a shutdown state where subcriticality is assured by physical means; or Note: For CANDU reactors, this refers to a guaranteed shutdown state. b) critical or sub-critical at any power where the normal (at high power) heat sinks are not the primary heat sinks. Note : Examples of high power heat sinks include steaming of boilers to turbine or condensers.

1.4 For the purposes of this Standard, the outage commences when the normal (at high power) heat sinks are no longer the primary heat sinks. The outage is considered to be terminated when the normal (at high power) heat sinks are re-established as part of the plan to proceed to sustained high power operation.

1.5 This Standard covers all systems that contribute to the transfer of heat by a) conveying heat to the ultimate heat sink; b) providing power or compressed air; c) providing inventory makeup to heat sink systems; or d) monitoring and control. Note : The combination of systems or portions of systems that contribute to these functions are referred to in this Standard as "heat sinks".